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首页> 外文期刊>Nuclear Technology >IMPLICATIONS FOR ADVANCED SAFEGUARDS DERIVED FROM A PROLIFERATION RESISTANCE AND PHYSICAL PROTECTION CASE STUDY FOR A GENERATION IV NUCLEAR ENERGY SYSTEM
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IMPLICATIONS FOR ADVANCED SAFEGUARDS DERIVED FROM A PROLIFERATION RESISTANCE AND PHYSICAL PROTECTION CASE STUDY FOR A GENERATION IV NUCLEAR ENERGY SYSTEM

机译:第四代核能系统的抗扩散和物理防护案例研究对高级安全防护的启示

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摘要

The Proliferation Resistance and Physical Protection Evaluation Methodology Working Group of the Generation IV International Forum produced a full-system case study on the Example Sodium Fast Reactor Nuclear Energy System (ESFR-NES). The ESFR-NES is a hypothetical fuel cycle complex consisting of four sodiumcooled fast reactors of medium size collocated with an on-site dry-fuel storage facility and a spent-fuel reprocessing facility based on electrochemical recycling technology. The complex recycles irradiated fuels from two feed streams, oxide fuel from off-site light water reactors and metal fuel from the on-site sodium-cooled fast reactors. Both of these streams are recycled on-site; uranium and transuranics are sent to the electrochemical reprocessing fuel cycle facility. The two streams combine and the fuel cycle facility creates new ESFR-NES metal fuel for the four on-site sodium-cooled fast reactors. The major safeguards concepts driving the safeguards analysis were timeliness goals and material quantity goals. Specifically, the recycled fuel, the in-process material in the fuelrnreprocessing facility, the off-site light water reactor spent fuel received at the ESFR-NES, and spent fuel from the on-site fast reactors will contain plutonium. The International Atomic Energy Agency defines the material within the ESFR-NES as "direct-use material" with a stringent timeliness goal of 3 months and a material quantity goal of 8 kg of plutonium. Furthermore, the ESFR-NES may have some intrinsic safeguards features if the plutonium and uranium are not separated during reprocessing. This facility would require major modifications to separate the plutonium from other transuranic elements in the reprocessed fuel. The technical difficulty in diverting material from the ESFR-NES is at least as strongly impacted by the adversaries' overall technical capabilities as it is by the effort required to overcome those barriers intrinsic to the nuclear fuel cycle. The intrinsic proliferation resistance of the ESFR-NES can affect how extrinsic measures in the safeguards approach for the complex will provide overall proliferation resistance.
机译:第四代国际论坛的防扩散和实物保护评估方法论工作组就示例钠快堆核能系统(ESFR-NES)进行了全系统案例研究。 ESFR-NES是一个假想的燃料循环系统,由四个中等大小的钠冷快堆组成,并配有现场干燃料存储设施和基于电化学循环技术的乏燃料后处理设施。该综合设施循环利用来自两种进料流的辐照燃料,非现场轻水反应堆的氧化物燃料和现场钠冷快堆的金属燃料。这两种流都在现场回收;铀和超铀酸被送至电化学后处理燃料循环设施。两种物流合并,燃料循环设施为四个现场钠冷快堆创造了新的ESFR-NES金属燃料。推动保障分析的主要保障概念是及时性目标和物料数量目标。具体而言,再循环燃料,燃料后处理设施中的加工材料,ESFR-NES接收的场外轻水反应堆乏燃料以及来自现场快堆的乏燃料将包含p。国际原子能机构将ESFR-NES中的材料定义为“直接使用材料”,其严格目标是3个月,and目标是8公斤。此外,如果在后处理过程中not和铀未分离,则ESFR-NES可能具有某些固有的安全保护功能。该设施将需要进行重大修改,以将the与后处理燃料中的其他超铀元素分离。攻击者从整体技术能力上对从ESFR-NES转移材料的技术难度至少与克服核燃料循环固有的障碍所需的努力一样强烈。 ESFR-NES固有的增殖抗性会影响该复合物保障措施中的外部措施如何提供总体的增殖抗性。

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